CN115831412A - Method and system for charging reactor - Google Patents
Method and system for charging reactor Download PDFInfo
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- CN115831412A CN115831412A CN202211515791.2A CN202211515791A CN115831412A CN 115831412 A CN115831412 A CN 115831412A CN 202211515791 A CN202211515791 A CN 202211515791A CN 115831412 A CN115831412 A CN 115831412A
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- 238000000034 method Methods 0.000 title claims abstract description 39
- 239000000446 fuel Substances 0.000 claims abstract description 89
- 238000000429 assembly Methods 0.000 claims abstract description 80
- 230000000712 assembly Effects 0.000 claims abstract description 80
- 238000012546 transfer Methods 0.000 claims description 35
- 238000005259 measurement Methods 0.000 claims description 26
- 230000007547 defect Effects 0.000 claims description 6
- 238000012544 monitoring process Methods 0.000 claims description 2
- 230000001902 propagating effect Effects 0.000 claims 1
- 230000008569 process Effects 0.000 abstract description 17
- 230000008859 change Effects 0.000 abstract description 7
- 238000007689 inspection Methods 0.000 description 7
- 230000006835 compression Effects 0.000 description 6
- 238000007906 compression Methods 0.000 description 6
- 239000002826 coolant Substances 0.000 description 6
- 238000004364 calculation method Methods 0.000 description 3
- 238000013461 design Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 229910001338 liquidmetal Inorganic materials 0.000 description 2
- 230000009257 reactivity Effects 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 230000007306 turnover Effects 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000004075 alteration Effects 0.000 description 1
- 229910052797 bismuth Inorganic materials 0.000 description 1
- JCXGWMGPZLAOME-UHFFFAOYSA-N bismuth atom Chemical compound [Bi] JCXGWMGPZLAOME-UHFFFAOYSA-N 0.000 description 1
- UDRRLPGVCZOTQW-UHFFFAOYSA-N bismuth lead Chemical compound [Pb].[Bi] UDRRLPGVCZOTQW-UHFFFAOYSA-N 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 238000013213 extrapolation Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000010412 perfusion Effects 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
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- 230000002285 radioactive effect Effects 0.000 description 1
- 230000035945 sensitivity Effects 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 238000013024 troubleshooting Methods 0.000 description 1
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The application relates to a reactor charging method, comprising loading a control assembly of a reactor into a core; after the control assemblies are loaded into the core, loading a plurality of fuel assemblies into the core in batches, wherein each batch of fuel assemblies is loaded into the core by the following steps: transferring the neutron source from the storage device to one side of the core; loading the fuel assemblies into a reactor core, wherein in the process of loading the fuel assemblies into the reactor core, neutron counting change is monitored by means of a neutron measuring device so as to prevent the reactor from reaching a critical state, and the neutron measuring device is arranged on the other side of the reactor core so as to enable the neutron measuring device to monitor neutrons which are emitted by a neutron source and propagate through the reactor core; after the fuel assemblies are loaded into the core, the neutron source is transferred back to the storage device. The present application further relates to a reactor charging system.
Description
Technical Field
The application relates to the technical field of reactors, in particular to a reactor charging method and a reactor charging system.
Background
The miniaturized reactor has the characteristics of long service life, high safety and the like, and generally adopts liquid metal, such as lead-based metal, as a coolant. Unlike conventional reactors, these liquid metal-cooled reactors can be charged in a dry-charging manner, i.e. without being filled with coolant, by completing the filling of all fuel assemblies in the plant and then transporting to the site of operation for coolant filling and critical operation. However, the related art fails to provide a method capable of achieving dry charging with sufficient safety.
Disclosure of Invention
In view of the above, the present application is made to provide a reactor charging method and a reactor charging system that overcome the above problems or at least partially solve the above problems.
According to a first aspect of embodiments of the present application, there is provided a reactor charging method comprising charging a control assembly of a reactor into a core; after the control assemblies are loaded into the core, loading a plurality of fuel assemblies into the core in batches, wherein each batch of fuel assemblies is loaded into the core by the following steps: transferring the neutron source from the storage device to one side of the core; loading the fuel assemblies into a reactor core, wherein in the process of loading the fuel assemblies into the reactor core, neutron counting change is monitored by means of a neutron measuring device so as to prevent the reactor from reaching a critical state, and the neutron measuring device is arranged on the other side of the reactor core so as to enable the neutron measuring device to monitor neutrons which are emitted by a neutron source and propagate through the reactor core; after the fuel assemblies are loaded into the core, the neutron source is transferred back to the storage device.
According to a second aspect of embodiments of the present application, there is provided a reactor charging system comprising: the hoisting assembly is used for loading the control assembly and the fuel assembly into the reactor core of the reactor; a storage device for storing a neutron source; a transfer device connected to the storage device for transferring the neutron source between the storage device and one side of the core; and the neutron measuring device is arranged on the other side of the reactor core and can monitor neutrons which are emitted by the neutron source and propagate through the reactor core when the neutron source is transferred to one side of the reactor core.
The reactor charging method and the reactor charging system provided by the embodiment of the application can ensure that the dry charging of the reactor can be safely completed.
Drawings
FIG. 1 is a flow chart of a method of charging a reactor according to an embodiment of the present application;
FIG. 2 is a flow chart of loading each batch of fuel assemblies into the core according to an embodiment of the present application;
FIG. 3 is a schematic diagram of an arrangement of a neutron source and a neutron measurement device according to an embodiment of the present application;
FIG. 4 is a schematic illustration of fuel assembly batch division according to an embodiment of the present application;
FIG. 5 is a schematic view of a reactor charging system according to an embodiment of the present application;
fig. 6 is a schematic view of a transfer device according to an embodiment of the present application.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more clear, the technical solutions of the present application will be described below in detail and completely with reference to the accompanying drawings of the embodiments of the present application. It should be apparent that the described embodiment is one embodiment of the present application, and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the described embodiments of the application without inventive effort, are within the scope of protection of the application.
It is to be noted that, unless otherwise defined, technical or scientific terms used herein shall have the ordinary meaning as understood by those of ordinary skill in the art to which this application belongs. If the description "first", "second", etc. is referred to throughout, the description of "first", "second", etc. is used only for distinguishing similar objects, and is not to be construed as indicating or implying a relative importance, order or number of technical features indicated, it being understood that the data described in "first", "second", etc. may be interchanged where appropriate. If "and/or" is presented throughout, it is meant to include three juxtapositions, exemplified by "A and/or B" and including either scheme A, or scheme B, or schemes in which both A and B are satisfied.
The embodiment of the application firstly provides a reactor charging method for completing dry charging of a reactor, wherein the dry charging of the reactor refers to the completion of the assembly of all fuel assemblies and other assemblies in an assembly plant, the reactor cannot reach a critical state in the whole assembly process, and after the charging is completed, the reactor is transferred to an operation site for filling of a coolant and critical operation. Reactors capable of dry-charging are mainly miniaturized reactors using liquid metal as coolant, such as lead bismuth fast reactors or other lead-based reactors, and sodium-cooled fast reactors, etc.
Referring to fig. 1, the method provided by the present application includes:
step S102: the control assemblies of the reactor are loaded into the core.
Step S104: after the control assemblies are loaded into the core, a plurality of fuel assemblies are loaded into the core in batches.
As described above, steps S102 and S104 can be performed in an assembly plant, and the skilled person can select the loading site according to the actual assembly requirement, without limitation.
In step S102, all control assemblies of the reactor, such as control rods of the reactor and the like, which are well known to those skilled in the art, are required to be inserted into the core, and the reactivity of the core and the scram and the like are generally controlled by the movement of the control assemblies in the core during the operation of the reactor. In step S102, all the control assemblies are inserted into the core, so that the maximum negative reactivity set in the design thereof is introduced into the core, and theoretically, all the fuel assemblies set in the design thereof cannot reach a critical state even though the core is inserted therein, thereby ensuring the safety of the dry charge.
In some embodiments, in addition to the control components, other components besides fuel components required for the operation of the reactor, such as stainless steel components commonly used in a bismuth-lead reactor, may also be loaded in step S102.
After all the control components of the reactor are inserted into the core in step S102, a plurality of fuel components may be loaded into the core in batches in step S104, and the specific batch division manner may be selected by those skilled in the art according to actual conditions, and the following relevant parts will also specifically relate to some batch division manners of the loading, and will not be described herein again.
After all of the fuel assemblies are loaded into the core, the reactor may be transferred to an operating site for coolant perfusion and critical operation.
Referring to fig. 2, when each batch of fuel assemblies is loaded into the core, the following steps may be specifically included:
step S202: the neutron source is transferred from the storage device to one side of the core.
Step S204: and loading the fuel assemblies into the reactor core, wherein during the process of loading the fuel assemblies into the reactor core, the neutron counting change is monitored by means of a neutron measuring device so as to prevent the reactor from reaching a critical state, and the neutron measuring device is arranged at the other side of the reactor core so as to enable the neutron measuring device to monitor neutrons which are emitted by the neutron source and propagate through the reactor core.
Step S206: after the fuel assemblies are loaded into the core, the neutron source is transferred back to the storage device.
It can be understood that although all the control assemblies have been loaded into the core in step S102, there is still a possibility of accidental criticality during the loading process, and for this reason, the neutron count variation during the loading process is monitored by means of the neutron measuring device in the present embodiment, so as to prevent the reactor from reaching the critical state and ensure the safety of the loading.
Further, because critical operation is not performed during charging, the neutron count that can be monitored by the neutron measurement device may be always at a lower level, in other words, the neutron measurement device may not work in a proper range, or even may not obtain an effective neutron count.
Specifically, referring to fig. 3, in the present embodiment, during the process of loading the fuel assembly into the core 10, the neutron source 11 will be transferred to one side of the core 10, and the neutron measuring device 12 will be disposed at the other side of the core 10, so that the neutron measuring device 12 can measure neutrons emitted by the neutron source 11 and proliferated through the core 10, and the addition of the neutron source 11 enables the neutron measuring device 12 to operate in a proper range of measurement, so that the neutron measuring device 12 can accurately monitor the neutron count change of the core.
The specific positions of the neutron source 11 and the neutron measuring device 12 can be specifically determined by those skilled in the art according to parameters such as the range of the neutron measuring device 12 used in the actual loading process and the relevant parameters of the core and the neutron source, so that the neutron measuring device 12 can work in a proper range on one hand, and on the other hand, can mainly detect neutrons proliferated by the core 10, and can avoid receiving neutrons which come directly from the neutron source 11 and do not proliferate by the core 10 as much as possible.
Further, some operators may be required to operate near the core during the loading process, particularly in the gaps where two adjacent batches of fuel assemblies are installed, transfer, inspection, etc. of the fuel assemblies may be required, and if the neutron source is kept on one side of the core throughout the loading process, there may be a risk of radioactive leakage. For this reason, in this embodiment, the neutron source is further transferred back to the storage device after each batch of fuel assemblies is loaded, and the neutron source is transferred to one side of the core before the next batch of fuel assemblies is installed, so as to further ensure the safety of operators near the core.
In summary, in the method provided by this embodiment, on one hand, all the control assemblies are inserted into the core before loading to ensure that no criticality occurs in the core loading process, on the other hand, a neutron measurement device is used to monitor neutron count changes in the loading process to ensure that no accidental criticality occurs in the loading process, and on the other hand, after each batch of fuel assemblies is loaded into the core, the neutron source is returned to the storage device, so that the time for the relevant operators to contact the neutron source in a short distance is reduced, and the safety is further improved.
In some embodiments, the neutron source may be transferred from the storage device to a preset position on the core side such that the neutron count measured by the neutron measurement device is not less than the preset value. As described above, the preset value may be determined based on parameters such as a range of a range, sensitivity, etc. of the neutron measurement device, and the preset value may be 2cps as an example.
The preset position may be determined by neutron calculations or based on preliminary experiments, for example, in some embodiments, the neutron source may be transferred from the storage device to one side of the core prior to loading the first batch of fuel assemblies; adjusting the position of the neutron source based on the neutron count of the neutron measuring device to determine a preset position; and after the preset position is determined, recording the neutron count of the neutron measuring device to be used as a neutron count background.
It will be appreciated that the value detected by the neutron measurement device prior to loading the first batch of fuel assemblies (i.e. when not already loaded) is a minimum value without changing the position of the neutron source, and that if the value detected by the neutron measurement device is not less than the predetermined value at that time, it is ensured that the value detected by the neutron measurement device will not be less than the predetermined value throughout the loading process, and for this purpose, the predetermined position can be determined by adjusting the position of the neutron source prior to loading the first batch of fuel assemblies. Further, after the preset position is determined, the neutron count of the neutron measuring device at the moment can be recorded to serve as the neutron count background, so that the variation of the neutron count can be calculated in the subsequent charging process.
In some embodiments, neutron count changes may be separately monitored by at least two different types of neutron measurement devices. For example, a BF may be used 3 Neutron measurement device and one 3 He neutron measurement device can be selected by a person skilled in the art according to actual situations. The safety can be further ensured by respectively monitoring the neutron counting change by at least two neutron measuring devices of different types, and accidental criticality is avoided.
In some embodiments, after the neutron count change is monitored, the number of fuel assemblies required to reach the critical state can be determined based on the neutron count change, and a person skilled in the art can calculate the number of fuel assemblies required to reach the critical state by using an extrapolation method and the like, without limitation. It will be understood that since the control assemblies of the reactor are fully loaded into the core when charging, the number obtained by calculation at this time should theoretically be greater than the number of fuel assemblies actually required to be loaded, whereas if the number obtained during the actual calculation is less than the number of fuel assemblies actually required to be loaded, there may be a risk of accidental criticality, requiring temporary stopping of the charging and troubleshooting.
Whether the risk of accidental criticality exists in the charging process can be judged quickly and accurately by calculating the number of fuel assemblies required for the critical charging. In some embodiments, if two or more types of neutron measurement devices are used to monitor neutron count changes, the number of fuel assemblies required for a critical condition may be calculated based on the data measured by these neutron measurement devices, respectively, and a subsequent determination made. In some other embodiments, those skilled in the art can also perform other suitable processing on the neutron count monitored by the neutron measurement device to determine the critical risk, which is not described herein again.
In some embodiments, when multiple fuel assemblies are batched into the core, the fuel assemblies may be loaded in order from the inner circle of the core to the outer circle of the core.
In some embodiments, it will be appreciated that the outermost turn of the core will typically have a greater number of fuel assemblies, and therefore, when fuel assemblies are loaded into the outermost turn of the core, the fuel assemblies may be loaded in at least two batches, with the fuel assemblies of each batch being spaced apart to avoid an increased risk of accidental criticality due to too many fuel assemblies being loaded into a batch.
Fig. 4 is a schematic diagram showing fuel assembly batch division employed in an embodiment, in which 30 fuel assemblies are planned to be loaded, and the four batches are a, B, C and D, the first batch is loaded with the 6 fuel assemblies with the reference a at the innermost circle, the second batch is loaded with the 6 fuel assemblies with the reference B at the second outer circle, the third batch is loaded with 9 fuel assemblies with the reference C at the outermost circle, and the fourth batch is loaded with the 9 fuel assemblies with the reference D at the outermost circle.
In some embodiments, the fuel assemblies are inspected before they are loaded into the core, the inspection of the fuel assemblies may be performed at a fuel storage warehouse, and after the inspection is completed, the inspected fuel assemblies may be transferred to the vicinity of the core by a transfer tool such as a transfer vehicle for subsequent loading.
In some embodiments, inspecting the fuel assembly may specifically include inspecting the fuel assembly for straightness and surface defects. As an example, a gauge may be used to detect straightness of the fuel assembly and visually inspect the fuel assembly for surface defects. In some other embodiments, for safety, the surface defect of the fuel assembly may be remotely inspected by means of a scanner, a camera, or the like, without limitation.
By way of example, when the fuel assembly is inspected, the fuel assembly transportation container can be horizontally hoisted to the turnover machine by the aid of the crane, and then the transportation container is turned from the horizontal state to the vertical state by the aid of the turnover machine, and the horizontal hoisting can increase safety in the hoisting process. After the transport container is inverted to an upright position, the upper end cap of the transport container may be opened and the fuel assembly lifted from the transport container and transferred to the fuel assembly over-gauge inspection platform receptacle using a crane and fuel assembly gripper to inspect for straightness and surface defects. After the inspection is passed, the inspected fuel assemblies are transferred to the socket of the transfer trolley by using the crane and the fuel assembly gripping apparatus, and the transfer trolley is driven to a special station of the loading platform near the reactor core so as to perform subsequent loading operation.
In some embodiments, the control assemblies, as well as other assemblies, such as stainless steel assemblies, may also be inspected for straightness and surface defects prior to installation into the core. The specific steps of the inspection can refer to the related steps of the inspection of the fuel assembly, and are not described in detail herein.
Embodiments of the present application also provide a reactor charging system, referring to fig. 5, including: a hoisting assembly 20 for loading a control assembly and a fuel assembly into the core 10 of the reactor; storage means 30 for storing the neutron source 11; a transfer device 40 connected to the storage device 30 for transferring the neutron source 11 between the storage device 30 and one side of the core 10; and a neutron measuring device 12 disposed at the other side of the core 10, wherein when the neutron source 11 is transferred to one side of the core 10, the neutron measuring device 12 can monitor neutrons emitted from the neutron source 11 and proliferated through the core 10.
The hoisting assembly may be an assembly for hoisting the control assembly and the fuel assembly, which is commonly used in the art, and may include a crane, a gripper, and other devices, and those skilled in the art may select the assembly according to actual needs, and will not be described herein again. The specific steps of using the above reactor loading system for loading the reactor can refer to the description in the relevant parts above, and will not be described in detail here.
In some embodiments, referring to fig. 6, the transfer device 40 comprises: a transfer pipe 41 having one end of the transfer pipe 41 connected to the storage device 30 and the other end extended to one side of the core 10; and a power member 42 for driving the neutron source 11 to move in the transfer pipe 41.
The transfer tube 41 may be any conduit capable of accommodating the neutron source 11 for movement therein and meeting the radiation shielding requirements, and is not limited thereto.
In some embodiments, the power element 42 may use air energy to drive the neutron source 11 to move, and specifically, the power element 42 may include an air compression device, which may be connected to the storage device 30 through a valve and a pipeline, when the neutron source 11 needs to be transferred from the storage device 30 to the core 10 side, the valve may be opened and air in the air compression device may be injected into the storage device 30, the neutron source 11 is driven to the core 10 side by the impact force of the air, and when the neutron source 11 needs to be transferred back to the storage device 30, the air may be extracted by the air compression device, and the suction force formed by the air compression device drives the neutron source 11 back to the storage device 30.
In some other embodiments, the power member 42 can also move the neutron source 11 by its own movement, for example, the power member 42 can include a slide block disposed in the transfer tube 41, and the neutron source 11 can be connected with the slide block, so that the neutron source 11 can be moved by the movement of the slide block.
In embodiments where air energy is used to drive the neutron source 11 to be transferred, the end of the transfer tube 41 extending to the core 10 may be provided with a stop to prevent the neutron source 11 from slipping out of the transfer tube 41.
Further, since the neutron source 11 is always transferred to the end of the transfer pipe 41 in such an embodiment, the transfer pipe may be configured to include a plurality of sub-pipes, such as shown in fig. 6, the transfer pipe 41 includes two sub-pipes 411 and 412, and the sub-pipes may be connected by a sliding connection, so that the extension length and/or the extension angle of the transfer pipe 41 may be changed, thereby facilitating the adjustment of the specific position of the neutron source 11 when transferring to the core 10 side during the actual operation.
In some embodiments, the transfer device may further comprise: one or more position sensors 43, one or more position sensors 43 being provided in the transfer tube 41 to monitor the position of the neutron source 11. In some embodiments, position sensors 43 may be disposed at both ends of the transfer pipe 41 to monitor whether the neutron source 11 reaches a designated position on one side of the core 10 and returns to the storage device 30 smoothly, and in some embodiments, a position sensor 43 may also be disposed at the middle of the transfer pipe 41 to control the transfer direction of the neutron source 11 in real time and position the neutron source 11 when it is externally jammed in the transfer pipe 41.
In some embodiments, the transfer device 40 may further include a pressure gauge and an alarm, the pressure gauge may be disposed at the air compression device to monitor the state of the air compression device and ensure the operation safety thereof, and the alarm may alarm when the pressure of the pressure gauge is abnormal, so that the relevant operator can perform timely treatment.
In some embodiments, the system may include at least two different types of neutron measurement devices 12, such as described above, and a BF may be employed 3 Neutron measurement device and one 3 He neutron measuring device.
It should be understood that the above-described embodiments are illustrative and should not be construed as limiting the present application, and that those skilled in the art may make variations, modifications, substitutions and alterations to the above-described embodiments without departing from the scope of the present application.
Claims (14)
1. A method of charging a reactor, comprising:
loading a control assembly of a reactor into a core;
after the control assemblies are loaded into the core, loading a plurality of fuel assemblies into the core in batches, wherein each batch of fuel assemblies is loaded into the core by the following steps:
transferring a neutron source from a storage device to one side of the core;
loading the fuel assemblies into the core, wherein during loading of the fuel assemblies into the core, neutron count changes are monitored by a neutron measurement device to avoid the reactor reaching a critical state, the neutron measurement device being disposed on the other side of the core to enable the neutron measurement device to monitor neutrons emitted by the neutron source and propagating through the core;
transferring the neutron source back to the storage device after the fuel assemblies are loaded into the core.
2. The method of claim 1, wherein transferring the neutron source from the storage device to one side of the core comprises:
and transferring the neutron source from the storage device to a preset position on one side of the reactor core, wherein the preset position enables the neutron count measured by the neutron measuring device to be not less than a preset value.
3. The method of claim 2, further comprising:
transferring the neutron source from the storage device to one side of the core prior to loading a first batch of the fuel assemblies;
adjusting a position of the neutron source based on the neutron count of the neutron measurement device to determine the preset position;
and after the preset position is determined, recording the neutron count of the neutron measuring device to be used as a neutron count background.
4. The method of claim 1, wherein monitoring for neutron count changes with the neutron measurement device comprises:
neutron count changes are separately monitored by at least two different types of neutron measurement devices.
5. The method of claim 1 or 4, further comprising:
determining the number of fuel assemblies needed to reach a critical state based on neutron count changes monitored by the neutron measurement device.
6. The method of claim 1, wherein when a plurality of the fuel assemblies are loaded in the core in batches, the fuel assemblies are loaded in an order from an inner circle of the core to an outer circle of the core.
7. The method of claim 6 wherein the fuel assemblies are loaded in at least two batches when loading the fuel assemblies to the outermost turn of the core, the fuel assemblies of each batch being spaced apart.
8. The method of claim 1, further comprising:
inspecting the fuel assemblies prior to loading the fuel assemblies into the core;
transferring the qualified fuel assemblies to the vicinity of the core.
9. The method of claim 8, wherein inspecting the fuel assembly comprises:
the fuel assembly was inspected for straightness and surface defects.
10. A reactor charging system comprising:
the hoisting assembly is used for loading the control assembly and the fuel assembly into the reactor core of the reactor;
a storage device for storing a neutron source;
a transfer device connected to the storage device for transferring the neutron source between the storage device and one side of the core;
and the neutron measuring device is arranged on the other side of the reactor core and can monitor neutrons which are emitted by the neutron source and propagate through the reactor core when the neutron source is transferred to one side of the reactor core.
11. The system of claim 10, wherein the transfer device comprises:
a transfer pipe having one end connected to the storage device and the other end extended to one side of the core;
and the power part is used for driving the neutron source to move in the transfer pipe.
12. The system of claim 11, wherein the transfer tube comprises a plurality of sub-tubes, the plurality of sub-tubes being slidably connected therebetween such that the extension length and/or extension angle of the transfer tube is changeable.
13. The system of claim 11, wherein the transfer device further comprises:
one or more position sensors disposed in the transfer tube to monitor a position of the neutron source.
14. The system of claim 10, wherein the system comprises at least two different types of the neutron measurement device.
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| CN114188046A (en) * | 2021-12-03 | 2022-03-15 | 中国原子能科学研究院 | Zero-power reactor starting control method and device |
| CN114420328A (en) * | 2022-01-10 | 2022-04-29 | 中国原子能科学研究院 | Method and device for monitoring reactor subcritical degree |
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